The TINTE print output file generally contains the following main data blocks, depending on the amount of output data requested by the user (see Section 6.3).
The additional TINTE console output is very similar, but does not contain the larger fields like the 2-d arrays, region heat balance and final transient history tables.
Output Block #1: Print of TINTE-User dialog.
Output Block #2: Print of the Input Blocks ST, GM, TZ, TM, and NZ, as contained in the .tn3 file.
Output Block #3:
This block starts with the following TINTE message:
NUKLEARE QUERSCHNITTE (Nuclear Cross-sections)
Es wurden Angaben zu einer Mischung aus 2 BE Typen gefunden.
(Input for 2 fuel element types were found) Temperatur-Rechnung. (Temperature calculation)
Das Volumen Der Gebiete Mit Heterogener Rechnung Betraegt 8.52720e+07 Cm**3, Das Der Einzelnen Regionen. (The volume of the model area that requires heterogeneous temperature calculations is:)
This means that TINTE has determined that the total volume of materials with heterogeneous temperature calculation is:
VTOTAL-TINTE = 8.52720E+07 cm3.
Since the heterogeneous temperature calculation has been specified only for materials in the core fuel region, the above figure is the total core volume. One should note here that this figure is usually slightly greater than the actual core volume, since TINTE ignores the graphite fraction in the conus region in the bottom of the core. The error as a result of this apprimation is acceptably small. The above TINTE messages are followed by a listing of the volumes of all the materials declared in input block TZ. Output Block #3 ends with TINTE message:
Die Nachwaermeberechnung erfolgt mit LIFE-Daten aus VSOP (the decay heat calcualtions using LIFE data from VSOP follows)
Daten fuer BE-Mischung eingelesen (Data for fuel elements read)
BENOETIGTER SPEICHERPLATZ (*8) 1703982 (required memory size) VORHANDENER SPEICHERPLATZ (*8) 2000000 (available memory size)
Output block #4
If a .tn3 file was read, this block starts with the TINTE message:
1 MASCHENBILD DES REAKTORS FUER T I N T E - RECHNUNG 0 TEMPERATUR - MATERIALBELEGUNG
The message is followed by a printout of the coarse and fine mesh grids, both axial and radial, that are used by TINTE for the temperature calculations.
Output Block #5
If the NZ block of the .tn3 file was read (nuclear regions definition), the next Output Block #5 is the coarse and fine mesh grids, both axial and radial, that are used by TINTE for the nuclear calculations.
It starts with the message:
1 MASCHENBILD DES REAKTORS FUER T I N T E - RECHNUNG 0 NUKLEARE MATERIALBELEGUNG
Output Block #6
Output block #6 starts with the TINTE message:
BITTE CPU- UND REAL-RECHENZEIT-SCHRANKEN (MIN), sowie ggf. Zeilenlaenge EINGEBEN ( 0 <=> KEINE BESCHRAENKUNG (bzw. 132 C/Z))
Output block #6 contains the output from TINTE equilibrium calculation if it is executed. The output parameters of each line of the iteration monitor, sent both to the output file and to the console, are described in Table 30.
Table 30: TINTE Equilibrium Iteration Monitor Output Description
Parameter Description CPUS CPU time [sec]
IFG Number of iterations done by TINTE for solid-to-gas heat tansfer calculation.
ITF Number of iterations done by TINTE for the solids temperature calculation.
VFT Maximum change [deg C] of solids’ temperature between two iteration steps.
IGS Number of iterations done by TINTE for gas flow calculation.
VGT Maximum change [deg C] of gas temperature between two iteration steps.
DP21 Pressure drop between second and first components of external flow network In this case: Pressure drop [mbar] between reactor outlet and reactor inlet.
P Pressure [bar] in second component of external flow network. In this case:
pressure at reactor outlet.
Parameter Description TK3 Gas temperature [deg C] in a material selected in the .tn3 file, e.g.: the CBCS
inlet.
MP1 Gas mass flow rate [kg/sec] in material reactor inlet.
WQK
Power [%] transferred by convection from fuel to gas. Note that this figure is never 100%, since radiation and conduction heat transfer also plays a small role.
A typical steady-state value is WQK = 99.55%, which means that convective heat transfer is responsible for transporting 398 MW of the 400 MW thermal power generated by the reactor.
BZTM Maximum fuel sphere centre temperature [deg C].
ITN Number of iterations done by TINTE for the nuclear calculation within one temperature iteration step.
VNL Maximum change [%] of reactor fission power between two iteration steps.
WQNF
Reactor fission power [%]. The global fission power is calculated as the
equilibrium power which would be attained for the current neutron flux. (During a transient, this field is a measure of the current fission rate in relation to the equilibrium fission rate – see Table 31). The difference between WQNF and WQNT (which occurs only during transients) should be noted by the user (see Table 31).
KEFF Effective multiplication coefficient.
There are nine more columns to the right from the KEFF one, but only in the printer output file. The output information in these coluimns is used to indicate for which material number, and in what coarse and fine mesh number, the maximum changes occur in the solid temperatures, the gas temperature, and the nuclear fission power. TINTE Output Block #6 ends with the messages:
0STATIONAERE RECHNUNG KONVERGIERT (The steady-state calculation converged).
0GENAUIGKEITSSCHRANKEN: EPANI EPSNO EPAFT EPABT EPAGT 2.E-05 1.E-04 2.E-01 2.E-01 2.E-01
(Various convergence criteria used are listed; cf. input block ST).
0T I N T E - RESTARTAUSGABE NACH STATIONAERER RECHNUNG 0RESTART-FILE 10 GESCHRIEBEN UND ABGESCHLOSSEN
(Restart file after equilibrium calculation written and closed).
TINTE Output Block #7
It contains the two-dimensional data arrays, that could occur in both the output and the .p2d binary files, if the user specified these options. The data arrays are as follows (in sequence as listed by TINTE):
• MOD. TEMP [K] Radial and axial mesh grid values of the average moderator temperature, used for nuclear feedback calculations [K]. This data is given in the nuclear material mesh grid, i.e. the grid defined in the NZ block of the .tn3 file. inside the core area, it is calculated as the average temperature of the fuel and fuel-free zones in a sphere (i.e. the average of all fine shells inside a sphere), over all fuel batches in a spatial mesh. Outside the core area, this field is equal to the “Feststoff”
i.e. areas that contain fuel. It is calcualted as the average temperature of the fuel zones in a sphere (i.e. the average of all fuel-containing fine shells inside a sphere), over all fuel batches in a spatial mesh. (The difference with respect to the Moderator temperature field above should be noted).
• RELATIVER GAS – DRUCK [mbar] Radial and axial mesh grid values of the gas pressure [mbar], relative to the reference pressure (which usually is defined at the reactor outlet).
• GAS – STROMDICHTE [KG/M**2*SEC] Radial and axial mesh grid values of the gas mass flowrate per unit area [kg/(m2*s)].
• Picture of the radial and axial gas flowrate vectors (if selected as an option).
• RADIALER-GASSTROM [KG/SEC/MASCHE] Radial mesh grid values of the gas mass flowrate [kg/s] (if selected as an option).
• AXIALER-GASSTROM [KG/SEC/MASCHE] Axial mesh grid values of the gas mass flowrate [kg/s].
• RAD.-KONVEKTION [MW/MASCHE] Radial and axial mesh grid values of the convective heat transferred in the radial direction [MW/mesh].
• AX.-KONVEKTION [MW/MASCHE] Axial mesh grid values of the convective heat transferred in the axial direction [MW/mesh].
• RAD. GAS-RANDTEM. /C Radial mesh grid values of the gas temperature for gas flowing in the radial direction [deg C]. Note that these temperatures are indicated on the mesh boundaries as axially averaged temperatures.
• AXI. GAS-RANDTEM. /C Axial mesh grid values of the gas temperature for gas flowing in the axial direction [deg C]. Note that these tempeeratures are indicated on the mesh boundaries as radially averaged temperatures.
• GAS – TEMPERATUREN /C Radial and axial mesh averaged values of the gas temperature [deg C].
• WAERMEUEBERGANGSZAHL ALPHA*F/V Radial and axial mesh grid values of the convective heat transfer coefficient [W/cm3*K].
• HE (N2, O2, CO, CO2, H2O, H2) - MOLENBRUCH IM GAS Mole fraction of the specific gas in the gas mixture.
• GAS-KONZENTRAZION Radial and axial mesh grid values of the gas concentration [mol/gas-m3].
• GRAPHIT - KORROSION / (MOL/M**3) Amount of corroded graphite.
• FESTSTOFF-TEMPERATUREN Radial and axial mesh grid values of the solid materials temperatures [deg C]. These temperatures are mesh-averaged data, and is used to define the interface temperature with the solid-to-gas heat transfer routines.
The field can be divided in 3 sections. In the case of the fuel in the core region, this field is euqal to the average fuel sphere surface temperature field for all fuel batches.
Outside the core region, the Feststoff temperaure field is equal to the Moderator field, up to the boundary of the neutronic mesh. Outside the neutronic mesh, it is the only field that indicates solid temperatures for metal and other ex-core structures.
• Temperaturen am BE-Rand /C “2” Radial and axial mesh grid temperature values [deg C] of type 2 pebbles at the surface of the fuel bearing part of the fuel sphere (R = 2.5 cm)
Note: The number of output fields here depends on the number of fuel types indicated by the .tn4 file.
• Temperaturen am BE-Zentr. /C “1” Radial and axial mesh grid values of type 1 pebbles central temperatures [deg C]
• Temperaturen am BE- Zentr. /C “2” Radial and axial mesh grid values of type 2 pebbles central temperatures [deg C]
(Note that the average values of the fuel surface and center temperatures for all batches are not equal to the “Moderator” or “Fuel” fields for all batches, since the averages for the
“Moderator” and “Fuel” fields are calculated from the fine shell temperatures inside the fuel spheres, which is not included in the current TINTE output).
• LEITFAEHIGKEIT RADIAL Radial mesh grid values of thermal conductivity for heat transfer in radial direction [W/cm*K]. Various correlations are used to calcuate these values, e.g. the Zehner-Schluender correlation for conductivity inside the pebble bed.
• LEITFAEHIGKEIT AXIAL Axial mesh grid values of thermal conductivity for heat transfer in axial direction [W/cm*K].
• KONVEKTIV ABGEFUEHRTE WAERME Radial and axial mesh grid values of the heat density transferred by convection [W/cm3]. Note that this is a heat density value, and not a heat per mesh value. Data will only be given in the meshes that were defined as gas flow meshes.
• LOKALE NUKLEARE WAERMEQUELLE Radial and axial mesh grid values of the heat (or power) density that was produced in the fuel by nuclear fission [W/cm3].
• alle nicht-lok. Waermequellen Radial and axial mesh grid values of all non-local heat density sources in [W/cm3], produced from all processes other than fission nuclear reactions, e.g. neutron absorption, fast neutrons thermalization, gamma-quanta absorption. This data are given in the core region, as well as in the reflector regions.
• davon Gamma-Transport Radial and axial mesh grid values of non-local heat density sources [W/cm3], produced from gamma-quanta absorption only.
• schneller Fluss Radial and axial mesh grid values of the fast neutron flux [1/cm2].
Note: The fast neutron flux in TINTE is neutrons with energies in the range 3.06 eV – 10 MeV.
• thermischer Fluss Radial and axial mesh grid values of thermal neutrons flux [1/cm2].
Note: The thermal neutron flux in TINTE is neutrons with energies less than 3.06 eV.
• Xe-Konzentration Radial and axial mesh grid values of Xe135 concentration [1/barn*cm].
• Jod-Konzentration Radial and axial mesh grid values of I135 concentration [1/barn*cm]
• VORGEGEBENE WAERMEQUELLE Radial and axial mesh grid values of additional
• KOMPONENTEN – NETZWERK External one-dimensional network description.
Output Block #8
TINTE Output Block #8 starts with the message :
MITTLERE TEMPERATUREN, WAERME-QUELLEN, -STROEME UND -BILANZEN and contains detail information for each material defined in TINTE Input Block TM, such as:
• Solid material temperature [deg C]: Average value for all nodes with the given material number.
• Gas temperatures [deg C]: Average values for all nodes with the given material number.
• Local nuclear heat sources in the material [MW].
• Non-local nuclear heat sources in the material [MW].
• Heat transfer by convection [MW].
• Heat transfer by conduction and radiation [MW].
• Heat transfer between the material and other materials, adjacent to it [MW].
TINTE Output Block #9 It starts wth message :
INSTATIONAERE RECHNUNG
This output block contains the TINTE output for the non-steady state (or transient) calculation (i.e. all data generated after t = 0 seconds). The time step monitor lines output parameters description is almost identical to that of the steady-state iteration monitor lines output (see Table 30), except that some output fields are unique to the transient calculation. The output fields that occur only during the transient calculation are summarised in Table 31.
Table 31: TINTE Transient Time Step Monitor Lines Output Description Parameter Description REAKT
Reactivity [mNile] needed to keep the reactor at the k-eff value as calculated during the steady-state run. This output field only occurs when a global reactor parameter ramp is performed.
OMNL
Inverse reactor period [1/s]. This field replaces the KEFF field during transients, and is an indication of the varaitions that occurs in the system’s global power density rate. The global inverse reactor period ω at any location in the reactor is defined /51/ such that the power density within the reactor changes according to the function
Parameter Description
WQNT
Total reactor thermal power [%]. The total power is calculated by summing the prompt and decay power to obtain the actual power produced in the reactor at any given time. This is in contrast to the fission power WQNF (Table 30), which is calculated as the equilibrium power which would be attained for the current neutron flux. This field is a measure of the current fission rate in relation to the equilibrium fission rate.
For time-dependent cases where power is increasing or has increased, the fission power will generally be greater than total power because the decay heat will be over-predicted (it is assumed to react promptly whereas in the real case decay heat will react very slowly to changes in power level). For decreasing power calculations, the fission power will be less than total power for the same reason.
It is suggested that power related plots be taken from the total and decay heat outputs, and that fission power (WQNF) be treated as an approximate measure of the current flux level.
DETFL Detected fission power [%]. This field represents the flux detector location as specified by the user in the NZ datablock of the .tn3 file.
RODP Actual control rod bank insertion position [cm]. (Output only during control rod motion ramps and during automated rod control “ramps”).
During the transient calculation, TINTE writes into the output file the same output blocks #7 and #8 as for the equilibrium run, but with the results from transient calculation at that specific timepoint. The user specifies these output timepoints by selecting the correct option in the .tn1 file (see control commands, section 8.3)..
Output Block #10
If TINTE has successfully completed a run and has reached the terminating control command “-3” (or –3.x, see section 8.3), it produces the final restart and/or p2d output fields and then prints an overview of any transient parts computed by issuing a series of transient history tables of all major scalar reactor variables for all temperature time steps.
After that, the run is ended with the final message:
TINTE – Programmende
If the user has chosen to end the .tn1 (or interactive console) input by the control command “-4” (see section 8.3), no transient history or further output is produced and a successful TINTE run is then simply terminated by the final message:
Tinte: STOP in Subroutine TIRSTI:
Steuerparameter -4 gelesen.